R.D. Kolasinski , J.D. Coburn , D.D. Truong , J.G. Watkins , T. Abrams , Z.Z. Fang , R. Hood , R.E. Nygren , A.W. Leonard , J. Ren , D.L. Rudakov , J. Sugar , C. Tsui , H.Q. Wang , J.A. Whaley , I. Bykov , A. Cruz , F. Glass , J. Herfindal , C. Lasnier , W. York
{"title":"分散增强钨材料暴露于分流等离子体时的再结晶、开裂和侵蚀","authors":"R.D. Kolasinski , J.D. Coburn , D.D. Truong , J.G. Watkins , T. Abrams , Z.Z. Fang , R. Hood , R.E. Nygren , A.W. Leonard , J. Ren , D.L. Rudakov , J. Sugar , C. Tsui , H.Q. Wang , J.A. Whaley , I. Bykov , A. Cruz , F. Glass , J. Herfindal , C. Lasnier , W. York","doi":"10.1016/j.nme.2025.101982","DOIUrl":null,"url":null,"abstract":"<div><div>In this study, we investigated the effects of combined intense particle and heat flux exposure on advanced tungsten plasma-facing materials within the DIII-D fusion facility. Our test matrix included two types of dispersoid-strengthened tungsten (containing either 100 nm diameter TiO<sub>2</sub> or Ni particles), along with high-purity polycrystalline tungsten as a reference. This experiment relied on a sample geometry angled at 15° relative to the divertor surface, thereby allowing the surfaces to intercept steady-state perpendicular heat fluxes (<span><math><mrow><msub><mi>q</mi><mo>⊥</mo></msub></mrow></math></span>) ranging from 10.1 to 19.6 MW/m<sup>2</sup>. During each shot, the samples were exposed to 42 Hz edge-localized modes (ELMs), allowing us to test the material response to transient heating. We correlated the exposure conditions with extensive post-test surface composition analysis and microscopy to determine how the plasma modified each surface. The angled specimens closest to the strike point received the highest combined heat and particle flux and melted midway through the experiment. EBSD analysis revealed they were completely recrystallized throughout, with an average grain size >100 µm. On the other hand, the specimens that received a lower steady state heat flux survived with more superficial surface damage. Whereas the high-purity polycrystalline tungsten exhibited a higher surface roughness, the dispersoid-strengthened material exhibited more extensive shallow inter-granular cracking. In addition, the surface was depleted of dispersoids following plasma exposure, possibly because of evaporation and/or sputtering. The results described here provide insights into the performance of these materials in a fusion environment which can guide further optimization for use in long-pulse devices.</div></div>","PeriodicalId":56004,"journal":{"name":"Nuclear Materials and Energy","volume":"45 ","pages":"Article 101982"},"PeriodicalIF":2.7000,"publicationDate":"2025-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Recrystallization, cracking, and erosion of dispersoid-strengthened tungsten materials during exposure to divertor plasmas\",\"authors\":\"R.D. Kolasinski , J.D. Coburn , D.D. Truong , J.G. Watkins , T. Abrams , Z.Z. Fang , R. Hood , R.E. Nygren , A.W. Leonard , J. Ren , D.L. Rudakov , J. Sugar , C. Tsui , H.Q. Wang , J.A. Whaley , I. Bykov , A. Cruz , F. Glass , J. Herfindal , C. Lasnier , W. York\",\"doi\":\"10.1016/j.nme.2025.101982\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In this study, we investigated the effects of combined intense particle and heat flux exposure on advanced tungsten plasma-facing materials within the DIII-D fusion facility. Our test matrix included two types of dispersoid-strengthened tungsten (containing either 100 nm diameter TiO<sub>2</sub> or Ni particles), along with high-purity polycrystalline tungsten as a reference. This experiment relied on a sample geometry angled at 15° relative to the divertor surface, thereby allowing the surfaces to intercept steady-state perpendicular heat fluxes (<span><math><mrow><msub><mi>q</mi><mo>⊥</mo></msub></mrow></math></span>) ranging from 10.1 to 19.6 MW/m<sup>2</sup>. During each shot, the samples were exposed to 42 Hz edge-localized modes (ELMs), allowing us to test the material response to transient heating. We correlated the exposure conditions with extensive post-test surface composition analysis and microscopy to determine how the plasma modified each surface. The angled specimens closest to the strike point received the highest combined heat and particle flux and melted midway through the experiment. EBSD analysis revealed they were completely recrystallized throughout, with an average grain size >100 µm. On the other hand, the specimens that received a lower steady state heat flux survived with more superficial surface damage. Whereas the high-purity polycrystalline tungsten exhibited a higher surface roughness, the dispersoid-strengthened material exhibited more extensive shallow inter-granular cracking. In addition, the surface was depleted of dispersoids following plasma exposure, possibly because of evaporation and/or sputtering. The results described here provide insights into the performance of these materials in a fusion environment which can guide further optimization for use in long-pulse devices.</div></div>\",\"PeriodicalId\":56004,\"journal\":{\"name\":\"Nuclear Materials and Energy\",\"volume\":\"45 \",\"pages\":\"Article 101982\"},\"PeriodicalIF\":2.7000,\"publicationDate\":\"2025-09-05\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Nuclear Materials and Energy\",\"FirstCategoryId\":\"101\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S2352179125001243\",\"RegionNum\":2,\"RegionCategory\":\"物理与天体物理\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Materials and Energy","FirstCategoryId":"101","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S2352179125001243","RegionNum":2,"RegionCategory":"物理与天体物理","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Recrystallization, cracking, and erosion of dispersoid-strengthened tungsten materials during exposure to divertor plasmas
In this study, we investigated the effects of combined intense particle and heat flux exposure on advanced tungsten plasma-facing materials within the DIII-D fusion facility. Our test matrix included two types of dispersoid-strengthened tungsten (containing either 100 nm diameter TiO2 or Ni particles), along with high-purity polycrystalline tungsten as a reference. This experiment relied on a sample geometry angled at 15° relative to the divertor surface, thereby allowing the surfaces to intercept steady-state perpendicular heat fluxes () ranging from 10.1 to 19.6 MW/m2. During each shot, the samples were exposed to 42 Hz edge-localized modes (ELMs), allowing us to test the material response to transient heating. We correlated the exposure conditions with extensive post-test surface composition analysis and microscopy to determine how the plasma modified each surface. The angled specimens closest to the strike point received the highest combined heat and particle flux and melted midway through the experiment. EBSD analysis revealed they were completely recrystallized throughout, with an average grain size >100 µm. On the other hand, the specimens that received a lower steady state heat flux survived with more superficial surface damage. Whereas the high-purity polycrystalline tungsten exhibited a higher surface roughness, the dispersoid-strengthened material exhibited more extensive shallow inter-granular cracking. In addition, the surface was depleted of dispersoids following plasma exposure, possibly because of evaporation and/or sputtering. The results described here provide insights into the performance of these materials in a fusion environment which can guide further optimization for use in long-pulse devices.
期刊介绍:
The open-access journal Nuclear Materials and Energy is devoted to the growing field of research for material application in the production of nuclear energy. Nuclear Materials and Energy publishes original research articles of up to 6 pages in length.